Irradiation embrittlement mitigation

Kari Törrönen, Reijo Pelli, Tapio Planman, Matti Valo

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

Abstract

Mitigation methods for reducing the irradiation damage on pressure vessel materials are reviewed: load leakage loading schemes are commonly used in PWRs to mitigate reactor pressure vessel embrittlement; dummy assemblies have been applied in WWER 440-type and in some old western power plants, when exceptional fast embrittlement has been encountered; shielding of the pressure vessel has been developed, but is not in common use; pre-stressing the pressure vessel has been proposed for preventing PTS failures, but its applicability is not yet demonstrated. The large number of successful annealing treatments performed in WWER 440 type reactors as well as research on the effects of annealing treatments suggest applications for western PWRs. The emergency core cooling systems have been modified in WWER 440-type reactors in connection with other mitigation measures.
Original languageEnglish
Title of host publicationSpecialists' Meeting on Irradiation Embrittlement and Optimization of Annealing
Place of PublicationParis
Pages351-379
Publication statusPublished - 1993
MoE publication typeB3 Non-refereed article in conference proceedings
Event1993 Specialists' Meeting on Irradiation Embrittlement and Optimization of Annealing - Paris, France
Duration: 20 Sep 199323 Sep 1993

Publication series

SeriesINIS Report
NumberNEA-CSNI-R--94-1
SeriesIAEA Conference Proceedings
NumberIWG-LMNPP 93/03

Conference

Conference1993 Specialists' Meeting on Irradiation Embrittlement and Optimization of Annealing
CountryFrance
CityParis
Period20/09/9323/09/93

Fingerprint

irradiation
vessel
mitigation
annealing
leakage
power plant
cooling
damage
reactor

Cite this

Törrönen, K., Pelli, R., Planman, T., & Valo, M. (1993). Irradiation embrittlement mitigation. In Specialists' Meeting on Irradiation Embrittlement and Optimization of Annealing (pp. 351-379). Paris. INIS Report, No. NEA-CSNI-R--94-1, IAEA Conference Proceedings, No. IWG-LMNPP 93/03
Törrönen, Kari ; Pelli, Reijo ; Planman, Tapio ; Valo, Matti. / Irradiation embrittlement mitigation. Specialists' Meeting on Irradiation Embrittlement and Optimization of Annealing. Paris, 1993. pp. 351-379 (INIS Report; No. NEA-CSNI-R--94-1). (IAEA Conference Proceedings; No. IWG-LMNPP 93/03).
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title = "Irradiation embrittlement mitigation",
abstract = "Mitigation methods for reducing the irradiation damage on pressure vessel materials are reviewed: load leakage loading schemes are commonly used in PWRs to mitigate reactor pressure vessel embrittlement; dummy assemblies have been applied in WWER 440-type and in some old western power plants, when exceptional fast embrittlement has been encountered; shielding of the pressure vessel has been developed, but is not in common use; pre-stressing the pressure vessel has been proposed for preventing PTS failures, but its applicability is not yet demonstrated. The large number of successful annealing treatments performed in WWER 440 type reactors as well as research on the effects of annealing treatments suggest applications for western PWRs. The emergency core cooling systems have been modified in WWER 440-type reactors in connection with other mitigation measures.",
author = "Kari T{\"o}rr{\"o}nen and Reijo Pelli and Tapio Planman and Matti Valo",
note = "CA: MET CA: REA Project code: MET30182",
year = "1993",
language = "English",
series = "INIS Report",
publisher = "International Atomic Energy Agency IAEA",
number = "NEA-CSNI-R--94-1",
pages = "351--379",
booktitle = "Specialists' Meeting on Irradiation Embrittlement and Optimization of Annealing",

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Törrönen, K, Pelli, R, Planman, T & Valo, M 1993, Irradiation embrittlement mitigation. in Specialists' Meeting on Irradiation Embrittlement and Optimization of Annealing. Paris, INIS Report, no. NEA-CSNI-R--94-1, IAEA Conference Proceedings, no. IWG-LMNPP 93/03, pp. 351-379, 1993 Specialists' Meeting on Irradiation Embrittlement and Optimization of Annealing, Paris, France, 20/09/93.

Irradiation embrittlement mitigation. / Törrönen, Kari; Pelli, Reijo; Planman, Tapio; Valo, Matti.

Specialists' Meeting on Irradiation Embrittlement and Optimization of Annealing. Paris, 1993. p. 351-379 (INIS Report; No. NEA-CSNI-R--94-1). (IAEA Conference Proceedings; No. IWG-LMNPP 93/03).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

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T1 - Irradiation embrittlement mitigation

AU - Törrönen, Kari

AU - Pelli, Reijo

AU - Planman, Tapio

AU - Valo, Matti

N1 - CA: MET CA: REA Project code: MET30182

PY - 1993

Y1 - 1993

N2 - Mitigation methods for reducing the irradiation damage on pressure vessel materials are reviewed: load leakage loading schemes are commonly used in PWRs to mitigate reactor pressure vessel embrittlement; dummy assemblies have been applied in WWER 440-type and in some old western power plants, when exceptional fast embrittlement has been encountered; shielding of the pressure vessel has been developed, but is not in common use; pre-stressing the pressure vessel has been proposed for preventing PTS failures, but its applicability is not yet demonstrated. The large number of successful annealing treatments performed in WWER 440 type reactors as well as research on the effects of annealing treatments suggest applications for western PWRs. The emergency core cooling systems have been modified in WWER 440-type reactors in connection with other mitigation measures.

AB - Mitigation methods for reducing the irradiation damage on pressure vessel materials are reviewed: load leakage loading schemes are commonly used in PWRs to mitigate reactor pressure vessel embrittlement; dummy assemblies have been applied in WWER 440-type and in some old western power plants, when exceptional fast embrittlement has been encountered; shielding of the pressure vessel has been developed, but is not in common use; pre-stressing the pressure vessel has been proposed for preventing PTS failures, but its applicability is not yet demonstrated. The large number of successful annealing treatments performed in WWER 440 type reactors as well as research on the effects of annealing treatments suggest applications for western PWRs. The emergency core cooling systems have been modified in WWER 440-type reactors in connection with other mitigation measures.

M3 - Conference article in proceedings

T3 - INIS Report

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BT - Specialists' Meeting on Irradiation Embrittlement and Optimization of Annealing

CY - Paris

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Törrönen K, Pelli R, Planman T, Valo M. Irradiation embrittlement mitigation. In Specialists' Meeting on Irradiation Embrittlement and Optimization of Annealing. Paris. 1993. p. 351-379. (INIS Report; No. NEA-CSNI-R--94-1). (IAEA Conference Proceedings; No. IWG-LMNPP 93/03).